05000280/LER-1979-025-03, /03L-0:on 790906,during Review of 1978 Reactor Coolant Activity Records,Discovered Excessive Reactor Coolant Activity Occurred & Not Reported.Iodine Spike Caused by Reactor Trip.Specific Sampling Program Initiated

/03L-0:on 790906,during Review of 1978 Reactor Coolant Activity Records,Discovered Excessive Reactor Coolant Activity Occurred & Not Reported.Iodine Spike Caused by Reactor Trip.Specific Sampling Program Initiated

ML19253B258
Person / Time
Site:	Surry
Issue date:	10/05/1979
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19253B256	List: 05000280/LER-1979-025, Forwards LER 79-025/03L-0 05000280/LER-1979-025-03, /03L-0:on 790906,during Review of 1978 Reactor Coolant Activity Records,Discovered Excessive Reactor Coolant Activity Occurred & Not Reported.Iodine Spike Caused by Reactor Trip.Specific Sampling Program Initiated
References
LER-79-025-03L-01, LER-79-25-3L-1, NUDOCS 7910100171
Download: ML19253B258 (2)

LER-1979-025, /03L-0:on 790906,during Review of 1978 Reactor Coolant Activity Records,Discovered Excessive Reactor Coolant Activity Occurred & Not Reported.Iodine Spike Caused by Reactor Trip.Specific Sampling Program Initiated

Event date:
Report date:
2801979025R03 - NRC Website

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Surry Power Station, Unit 1 Docket No: 50-280 Attachment: page 1 of 1 Report No: 79-025 /03L-0 Event Date: 9 /6/79 Title of Report:

Excessive Reac tor Coolant Ac t ivity 1.

Description of Event

A review of last year's reactor coolant activity revealed that the specific activity of the primary coolant was 1.15 uCi/ gram dose equivalent 1-131 following a reactor trip at 19% power level.

This event is contrary to Appendix A-1 to DPR-32 of the Technical Specifications, and was reportable under T.S. 6. 9.1.

However, a report was not submitted at that time.

2.

Probable Consequences and Status of Redundant Systems:

Appendix A.1 specifies that a sampling program must be initiated within 2 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following a thermal power change exceeding 15 percent of rated thermal power (Table 3.1.D-1.4(b)), and sampling repeated every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> whenever the specific activity is greater than 1.0 uCi/ gram dose equivalent I-131.

This appendix allows continued operation for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided operation time does not exceed 10% of unit's total yearly operating time.

3.

Cause

The iodine spike resulted from a reactor trip.

4.

Immediate Corrective Action

The immediate corrective action was the initiation of the specific activity sampling program.

5.

Subsequent Corrective Action:

No additional corrective action was required, because the sampling program eventually indicated a specific activity less than 1.0 uCi/ gram dose equi-valent I-131.

6.

Actions Taken to Prevent Recurrence:

Future occurrences of this type will be evaluated, and if necessary, reported expeditiously.

7.

Generic Implications:

None

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